ENDF/B-VII.1 Neutron Cross Section Data Testing with Critical Assembly Benchmarks and Reactor Experiments

Nuclear Data Sheets

Volumn 112, Issue 12, 2011, Pages 2997-3036

  Kahler, A C ^a   MacFarlane, R E ^a   Mosteller, R D ^a   Kiedrowski, B C ^a   Frankle, S C ^a   Chadwick, M B ^a   McKnight, R D ^b   Lell, R M ^b   Palmiotti, G ^c   Hiruta, H ^c   Herman, M ^d   Arcilla, R ^d   Mughabghab, S F ^d   Sublet, J C ^e   Trkov, A ^f   Trumbull, T H ^g   Dunn, M ^h  

^a LOS ALAMOS NATIONAL LABORATORY   (United States)

^b ARGONNE NATIONAL LABORATORY   (United States)

^c IDAHO NATIONAL LABORATORY   (United States)

^d BROOKHAVEN NATIONAL LABORATORY   (United States)

^e CULHAM SCIENCE CENTRE   (United Kingdom)

^f JO EF STEFAN INSTITUTE   (Slovenia)

^g Knolls Atomic Power Laboratory   (United States)

^h OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CRITICALITY (NUCLEAR FISSION); EIGENVALUES AND EIGENFUNCTIONS; FISSION PRODUCTS; HANDBOOKS; NEUTRON SCATTERING; NEUTRONS; NUCLEAR FUELS; PRESSURIZED WATER REACTORS; REACTION RATES; URANIUM; URANIUM DIOXIDE;

CRITICAL ASSEMBLY; CRITICALITY SAFETY; CROSS SECTION DATA; CROSS-SECTION LIBRARY; DATA TESTING; EIGEN-VALUE; EVALUATED NUCLEAR DATA FILE; NEUTRON CROSS SECTIONS; NUCLEAR DATA; SOLUTION SYSTEM;

LIBRARIES;

EID: 84855947515     PISSN: 00903752     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nds.2011.11.003     Document Type: Article

References (22)

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